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Time Behavior of Fuel Concentrations in Single-Region Reactors Containing U-233, U235, Th-232 and Fission Product Poisons
Analytical expressions were obtained for the time behavior of fuel concentrations and fuel-feed rates in single-region, spherical, UO3-ThO2-D2O reactors.
Date:
February 26, 1957
Creator:
Gilbert, Nathan & Kasten, Paul R.
Object Type:
Report
System:
The UNT Digital Library
Capillary Flowmeter
The HRT leak detector system consists of four headers each of which are connected on one side to a common supply of pressurized water and on the other side by individual tubing to the ring grooves of approximately twenty flanges. There are two methods of detecting the loss of water that are particularly applicable to the HRT: (1) By the loss of pressure in a constant volume system; (2) By the measurement of flow from a constant pressure system. It was determined to investigate the second method which requires a flowmeter capable of measuring flows of .5 cc or less of water per hour. The experiment flowmeter constructed performed almost exactly as the design calculations predicted.
Date:
February 20, 1957
Creator:
Hise, E. C.
Object Type:
Report
System:
The UNT Digital Library
Cross Sections for OCUSOL-A Program
The OCUSOL-A program (ORNL-CF-57-6-4) for Univac is a modification of the Eyewash (ORNL-1925) multi-group, multi-region reactor code. The group=energy-lethargy-temperature relationship are given in Table A. The element code numbers are given in Table B. The cross sections now on the sigma-tape are given in tables in the Appendix numbered with the element code number. This technical report explains the bases for choosing the cross sections.
Date:
June 11, 1957
Creator:
Roberts, J. T. & Alexander, L. G.
Object Type:
Report
System:
The UNT Digital Library
Specifications for Cleanliness Requirements High Level Volatility Lab. 4507
Specifications are presented for cleanliness during installation of piping and equipment in the High Level Volatility Laboratory, Bldg. 4507.
Date:
June 6, 1957
Creator:
Ruch, J. B.
Object Type:
Report
System:
The UNT Digital Library
Effect of Slurry Physical Properties on Heat Exchangers and Pump Characteristics
Design calculations were made for a system consisting of a pump, one hundred feet of pipe, and a heat exchanger to remove 1 Mw of heat from various aqueous thorium oxide slurries. The rheological properties of the slurries were varied over a range of yield stresses from 0 to 1.5 lb/sq ft and of coefficients of rigidity from 1/2 to 2 centipoise. Two different cases were studied: a heat exchanger having fixed axial and radial delta T in which the tube length was allowed to vary and a heat exchanger having fixed tube length in which the axial and radial delta T were allowed to vary. It was shown that the pump power must be increased by a factor of 15 to 30 in order to maintain satisfactory operation of the heat exchanger as the slurry yield stress is increased form 0 to 1.5 lb/sq ft. However the pump power is essentially independent of heat exchanger tube diameter for any given slurry. The rated capacity of a slurry heat exchange is essentially independent of slurry yield stress and coefficient of rigidity, provided that the tube velocity can be suitably increased as the slurry yield stress in increased.
Date:
June 10, 1957
Creator:
Thomas, D. G.
Object Type:
Report
System:
The UNT Digital Library
Observed performance of the Fuel Sample Cooler
Measurements of flow rate through the fuel high-pressure system sampler indicate that the average flow rates is about 0.29 gpm (145 lb/hr) plus or minus 50%, which affords an adequate purge of from 12 to 36 volumes through the sample line if the full fifteen minutes of purging is allowed before isolating the sample. The fuel sample cooler was fund to have adequate capacity to reduce the temperature of the fuel solution form about 275 to 70 C, using pre-heated cooling water at 70 C. Uncertainties in temperature measurements make it impossible to estimate an observed over-all heat transfer coefficient.
Date:
June 3, 1957
Creator:
Van Winkle, R. & Wiethaup, R. R.
Object Type:
Report
System:
The UNT Digital Library
Observed Net Heat Loss from the HRT High-Pressure System
An estimate has been obtained of the heat that should be generated in the HRT core in order to hold the system at operating temperature under no-load conditions. This estimate was made by measuring the feed-water rate to the package boiler during an oxygenated water rung. Results are summarized.
Date:
June 4, 1957
Creator:
Van Winkle, R. & Wiethaup, R. R.
Object Type:
Report
System:
The UNT Digital Library
The Disposal of Power Reactor Waste Into Deep Wells
For various reasons it is not possible to leave the uranium or other nuclear fuel in a power reactor until all of it has been "burned up" by fission. In the case of liquid fuel (homogeneous) reactors a small part is continuously bled out, purified and returned. In the case of solid fuel reactors, fuel elements are periodically removed, reprocessed and the "unburned" fuel put back into service. In both cases the purification produces wastes which contain radioactive fission products and transuranic elements, and it is with the disposal of these wastes that we are concerned. For technical reasons, we will limit our consideration to the wastes from the processing of solid fuel elements, and from the processing of the very similar solid "blanket" elements in which fissionable fuel is made from non-fissionable isotopes of uranium and thorium by interaction with neutrons in the outer regions of the nuclear reactor.
Date:
June 13, 1957
Creator:
De Laguna, Wallace, 1910- & Blomeke, J. O.
Object Type:
Report
System:
The UNT Digital Library
HRT Letdown Valves
To supply information about the several letdown valves which have been in HRT service, a typical valve plug examined by the Metallurgy Section confirms the belief that chemical attack on the Stellite #6 was occurring. It appears that most of the corrosion was due to rinse solutions, since this phenomenon has not been noted on letdown valves in the HRT Mockup where over 90% of the operating time has been with UO2SO4 solutions.
Date:
June 5, 1957
Creator:
Billings, A. M.
Object Type:
Report
System:
The UNT Digital Library
September, 1956, Measure of Radiation level of HRE Fuel System Components (After Storage for 27 Months)
Radiation level measurements of various HRE fuel system components, made in September, 1956, after 27 moths of storage, are compared with the June, 1954, readings before storage. Measurements were made with a standard cutie pie and results tabulated.
Date:
June 5, 1957
Creator:
Haynes, T. E. & Van Winkle, R.
Object Type:
Report
System:
The UNT Digital Library
Chemical Cleaning and Storage of the HRT Steam and Closed Cooling Water Systems
A 10% phosphoric acid solution contain 0.2% "Rodine 45" inhibitor is recommended to be used for the chemical cleaning of the HRT seam and closed colling water systems. Wet storage is recommended for both of these systems. The steam system is to be stored with steam condensate containing 100 ppm hydrazine, and closed cooling water system is to be stored with steam condensate containing 1000 ppm potassium chromate.
Date:
June 5, 1957
Creator:
McLain, Howard A.
Object Type:
Report
System:
The UNT Digital Library
The Reaction of Zirconium with Uranium Dioxide
An investigation of the causes of observed explosive reaction of zirconium-coated uranium dioxide on dissolution in nitric acid was conducted. It was concluded that such a reaction is to be expected. Possible but unconfirmed methods of alleviating the problem are suggested.
Date:
June 11, 1957
Creator:
Robinson, M. T.
Object Type:
Report
System:
The UNT Digital Library
HRP In-Pile Corrosion Test Loops -- Operation of In-Pile Loop L-2-10
Loop L-2-10 was the eighth completed in-pile loop experiment and the first in the HB-2 beam hole at the LITR. The loop was inserted on July 2, 1956 and removed on September 3, 1956. The installation, operation, removal, and general performance of the HRP in-pile solution corrosion loop in the HB-2 beam hole at the LITR are described.
Date:
June 13, 1957
Creator:
Walter, F. J.
Object Type:
Report
System:
The UNT Digital Library
Fuel Exposures in Heterogeneous Thorium Breeder Reactors
This technical report summarizes some preliminary calculations of fuel exposures attainable in heterogeneous reactors, fueled with a mixture of thorium and U233, moderated with D2O and operated with no net loss in fissionable fuel.
Date:
June 13, 1957
Creator:
Prince, B. E. & Jaye, S.
Object Type:
Report
System:
The UNT Digital Library
Summary of Corrosion Data for HRT Mockup Operational Period Ending February 16, 1957
The HRT mockup was shut down February 16, 1957 after operating for 576 hours on high concentration uranyl sulfate. At this time, all corrosion samples in the system were removed and replaced, and the wire extending thought the letdown hear exchanger was removed of examination.
Date:
June 17, 1957
Creator:
Wacker, R. E. & Griese, J. C.
Object Type:
Report
System:
The UNT Digital Library
Liquid-Liquid Extraction of Uranium and Plutonium from Hydrochloric Acid Solution with TRI (Iso-Octyl) Amine. Separation of Uranium and Plutonium from Thorium and Fission Products
A new and rapid method for the liquid-liquid extraction of uranium and plutonium from hydrochloric acid solution is based on the use of tri(iso-octyl)amine dissolved in xylene or methylisobutylketone. Uranium and/or plutonium are separated from thorium, alkalis, alkaline earths, rare earths, zirconium, niobium, ruthenium and other elements which do not form anionic species under the conditions described. The technique may be used for either tracer or macro quantities of uranium. Several practical applications of the method for the separations chemist are proposed.
Date:
June 18, 1957
Creator:
Moore, Fletcher L.
Object Type:
Report
System:
The UNT Digital Library
Spectrophotometric Determination of Cerium with Tiron
A spectrophotometric method for the determination of cerium with Tiron (disodium-1,2-dihydroxybenzene-3,5disulfonate) was applied to the determination of cerium in samples which contain uranium and zirconium. The cerium-Tiron complex in solutions of pH 8 or greater exhibits an absorption maximum of 500 mu . This reagent does not react with any other lanthanide element. The interference of iron, uranium, and zirconium was eliminated by extracting these interfering elements with a solution of trioctylphosphine oxide in cyclohexane. (auth)
Date:
June 14, 1957
Creator:
McDowell, B. L.; Meyer, A. S., Jr. & White, J. C.
Object Type:
Report
System:
The UNT Digital Library
Test Results on a Heater-Cooler Unit for the ORR In-Pile Loop
Tests have been completed on a combination heater-cooler unit for use in in-pile loops designed to operate in beam hole HN-1 of the ORR facility. The unit is designed to use air-water mixtures as the coolant. the coolant flows through a spiral of 3/8-inc. diameter tubing cast in aluminum around the 3/8-in. IPS loop pipe. four 1000-w calrod-type electric heating elements are cast into the aluminum, along with the cooling coils to provide loop heating.
Date:
June 28, 1957
Creator:
Mauney, T. H. & Savage, H. C.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Loop Components and Admixed Thorium-3% Uranium Oxide Slurry in 200A Loop (Summary of Run 200A-10)
A slurry addition system, a venturi in the circulation loop, and two types of sampling systems were tested with 500 and 800 g Th/kg H2O slurries in the 200 gpm loop at 250 C and 1000 psig. The addition system worked satisfactorily while the venturi gave erratic readings during part of the run. Both the capillary and in-line sampling systems proved satisfactory with the capillary sampler being much easier and more convenient to operate. The addition of uranium to the slurry had no appreciable effect on the handling characteristics, the attack rate on 347 SS, the particle size and crystallite size of the thorium oxide. The attack rate was found to be 1 mpy during the first 100 hours of circulation and decreased to 0.4 mpy at the end of the run.
Date:
June 13, 1957
Creator:
Gallaher, R. B.; Kitzes, A. S. & VandenBulck, C. F.
Object Type:
Report
System:
The UNT Digital Library
Uranium-235 Abundance by Gamma Spectrometry
Techniques are described for determining U-235 abundance by measurement of the intensity of 0.18 Mev gamma radiation. One method involves measurement of the ratio of the intensity of 0.18-Mev radiation to that of 0.1 Mev radiation. The preferred technique consists of chemical separation of uranium followed by direct counting of 0.18-Mev photons. Application has been made in analysis of uranium samples of abundances in the range of 0.05% to 93%. Accuracy appears to be better than 3% if the abundance is between 0.7% and 100%. Findings in the self-absorption of 0.18 Mev radiation in uranium oxide are presented.
Date:
January 2, 1957
Creator:
Reynolds, S. A. & Eldridge, J. S.
Object Type:
Report
System:
The UNT Digital Library
Dynamic Corrosion Screening Tests on Inconel and Nickel in NaCl-MgCl2-UCl3 Bath
Nickel is more susceptible to mass transfer in a 100hr non-isothermal dynamic corrosion system than is Inconel when exposed to a NaCl-MgCl2-UCl3 (50.0-33.3-16.0 mole %) bath at a hot zone temperature 1800 F. No nickel mass transfer was observed in a 500-hr test at 1350 F, but Inconel showed some attack under these conditions. Inconel mass transfer was observed in both tests, being more severe at the higher temperature. On the bases of these preliminary tests, it appears that nickel is a more satisfactory container than Inconel for the chloride bath at temperatures in the region of 1350 F. The chromium is more susceptible to selective leaching from Inconel at 1800 F during a short 100-hr test (0.26% Cr in bath) than in a 500-hr test (<0.001% Cr in bath) at a lower temperature (1350 F ).
Date:
June 19, 1957
Creator:
Jansen, D. H.
Object Type:
Report
System:
The UNT Digital Library
Trip to Selas Corporation of America
On May 23, 1957, a visit was made by the writer to the Selas Corporation of American in Dresher, Pennsylvania. The purpose of the visit was to discuss further investigations into methods of tubesheet brazing by direct heating. Original work along these lines has been carried out at ORNL and is covered by a memo (CF-57-4-57) to W.D. Manly, dated April 16, 1957, and entitled : Investigation of Tubesheet Brazing by a Method of Direct Heating.
Date:
June 18, 1957
Creator:
Franco-Ferreira, E. A.
Object Type:
Report
System:
The UNT Digital Library
Fused Salt Compositions
The compositions of the compounds and fused salt mixtures referred to in the ANP project by numbers are given.
Date:
June 20, 1957
Creator:
Barton, C. J.
Object Type:
Report
System:
The UNT Digital Library
The Volatilization of Fission Products by Melting of Reactor Fuel Plates
Experiments in the controlled melting of irradiated fuel specimens, particularly of the APPR, STR, and MTR types have confirmed that prolonged heating in air at temperatures in excess of the melting point results in the release of a large portion of the radioactivity. On the other hand, a moderate amount of heating in air or steam sufficient only to melt a specimen results mainly in the partial volatilization of the rare gases; the halogens, iodine and bromine; and the alkali metals, cesium and rubidium. In the presence of air or water vapor, strontium and other fission products are not released. At trace concentration of fission products, slow melting of the APPR plate at 1525 C in air or steam effected the release of 50 percent of the rare gases, 33 percent of the iodine, 9 percent of the cesium and traces of strontium. After 25% burn-up, the cesium value increased to about 60 percent. Aluminum alloy of the MTR type, also at trace concentration, upon melting at 700 C released up to 2 percent of the iodine, 10 percent of the rare gases, and negligible portions of other fission products. Zirconium alloy of the STR type after 15 percent burn …
Date:
July 15, 1957
Creator:
Parker, Geogre W. & Creek, George E.
Object Type:
Report
System:
The UNT Digital Library